ML20082D980

From kanterella
Jump to navigation Jump to search
Rev 2 to QA02.02, QC Insps
ML20082D980
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 06/21/1988
From:
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML20081E364 List:
References
FOIA-90-570 QA02.02, QA2.02, NUDOCS 9107300222
Download: ML20082D980 (54)


Text

.. _ _ _ - _ _ _ - - _ _ .

\,I F CONTROLLED BY USER

.. ? . --

4

-s

/.'

DOC NO: QA02.02

/ REVISION: 2

[ FwE OF l DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS REC 02.D OF REVISIONS l

1 REVISION DATE l l

0 08/31/87 l Supersedes Procedurs 6N417.11.00 1 05/02/88 [ Incorporate Inspection Handbook & PRB comments 2 06/21/88 l Complete rewrite due to organi ational changes I

l

, 1 O l l

l l

l I

I i

l l

l 9107300222 910603 PDR FOIA PDR JONES 90-D70 Revi 'ed By: -

t valuation Required?

- _ d "c7MW Yes s[ No

" Quality Assurance o

6. MJ Cb'.3/4h Date PRB Review 51gnature, if reg'd Date Approved Pr, Effective Date:

/

Signature

' ,CM

/

bh

/ae D

9fil BB t '

V. P.,

ule Nuclehr Prod. Signature, if required Date JJL}

[

\ i '[ ') J E 7 [b, i

i e-khI, DOC. NO: QA02.02 REVISION: 2 PAGE 1 OF 50 DAT' ./21/88 Arizona Nuclear Power Project TIT 12: QUALITY CONTROL INSPECTIONS 1.0 PURPOSE nND SCOPE 1.1 Provides instructions for the uniform determination, identification, planning, performance and documentation of Quality Control inspections at PVNCS.

1.2 The scope of this Procedure includes work o.1 quali ty-related structures, systems, or components.

1.2.1 Peceiving, shipping and storage inspection is not within the scope of this Procedure.

1.2.2 Testing is not defined within the scopa of t.is Procedure; however, inspection of work performed during testing shall meet the requirements of this procedure (unless noted otherwise).

,,,, 1.2.3 Non-Destructive Examination and Sect 1 n XI Inservice

}((} Inspection are not within the scope of this procedure.

! 1.2.4 Independent verification by a so;ond person knowledgeable in the activity is not within the scope of this procedure.

1.3 The work documents as referred to in this procedure shall include, bu-are not limited to the following:

1.3.1 Work Orders (ccrrettive usintenance and preventive maintenance) 1.3.2 Station Manual Procedures that describe work 1.3.3 Contractor Wor!: Procedures .

e*

PY216-08 A 1444)

. . - . . _ . ~ . - . .. . - -- --

CONTROLLED BY USER j ~g ~:. -

/

DOC NO: QA02.02 3

/ REVISION: 2

  1. PAGE OF i DATE: 06/21/88 i Arizona Nuclear Power Project TITLE:- QUALITY CONTROL INSPECTIONS RFCORD OF REVISIONS I

l REVISION DATE l 1

0 08/31/87 l Supersedes Proccdurs 6N417.ll.00 1 05/02/88 l Incorporate Inspection Handbook & PRB comments 2 06/21/88 l Complete rewrite due to organitational changes I

l-

, 1 O i l

I i

i l

i I

.l -

i

.I 3

I (i

l . Q Revi 'ed By: ryJ. Evaluation Required?

- _ d -GMW Yes t / Nc, Alt/

' c-

" Quality Assurance lb_V. k &&

Date PRB Review Signature, if reg'd chon Date Apptf.ved Effective Date:

Q /G Signature /

mm 6fo/W

/ Datn

,lnIe8

/ ' I uk V. P., Nuclchr Prod. Signature, if required Date

3 DOC NO: QA02.02

$;f'. REVISION: 2 PAGE 1 0F 50 DATE: 06/21/88

- Arizona Nuclear Power Project TITLE: QUAL 5TYCONTROLINSPECTIONS 1.0 PURPOSE AND SCOPE 1.1 Provides instructions for the uniform determination, identification, planning, performance and documentation of Quality Control inspections at PVNCS.

1.2 The scope of this Procedure includes work on quality-related structures, systems, or components.

1.2.1 Receiving, shipping and storage inspection is not within the scope of this Procedure.

1.2.2 Testing is not defined within the scope of this Procedure; however, inspection of work performed during testing shall meet the requirements of this p:ocedure (unless noted otherwise).

,,, 1.2.3 Non-Destructive Examinat4.on and Section XI Inservice Aj]-) Inspectirn are not within the scope of this procedure.

1.2.4 Independent verification by a second person knowledgeable in the activity is not within the scope of this procedure.

1.3 The work documents a, referred to in this procedure shall include, but 1

are not limited to che following:

l l

1.3.1 Work Orders (corrective maint,enance and preventive maintenance) l 1.3.2 Station Manual Procedures that describe work l

l 1.3.3 Contractor Work Procedures ,

a o z*

.rh I

, t0 FY21MA (4 44

l DOC. NO: QA02.02 . l REVISION: 2 ,i PAGE 2 0F SO l DATE: 06/ l/88 l Arizona Nuclear Power Project ,'

TITLE: QUALITY CONTROL INSPECTIONS 2.0 RESPONSIBILITIES ,l 2.1

'l Department Managers and Section Supervisors are responsible for  !

determining and identifying acceptance requirements by including the j acceptance requirements in all procedures prepared by their department i for work they are responsible for on quality-related systems, structures, or components.  !

2.2 F!rst Line Work / Test Supervisor is responsible for the following:

2.2.1 Quality of all work performed under their supervision.

2.2.2 Notifp ng the Quality Control Department of inspection points '

prior to the performance of wo;k.

2.3 The Quality Control Department is rgsponsible for: l 2.3.1 Reviewingandconcurring.titballStationManualprcceduresa[

contractor sork procedures / instructions describing {

quality-related work and inspection, j 2.3.2 Reviewing and approving all work orders describing quality-related work and inspections to include the inserting and/or validating of inspection points.

2.3.3 Reviewing and approving all changes and revisions to this procedure.

2.3.4 Reviewing and approving special inspection plans.

3.2.5 Performing and documenting quslity inspections through the use of the approved Work Documents.

2.3.6 Approving and documenting inspection requirement changes, as necessary, during the performance of the work.

2.3.7 Concurring with the use of personnel, other than ANPP Quctity Control Personnel, to perform 1 tspections.

2.3.3 Documenting any deficiency discovered during the performance of inspecting in accordance with the appropriate procedures (Reference 5.1.4 and 5.1.5).

ma*. a+, --

,17'-

"6 DOC. bO: QA03.02 f REVISION: 2 i PAGE 3 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS 3.0 PROCEDURE 3.1 De te rmina ti on Personnel preparing construction, maintenance, modification or other '

work documents (3ncluding amendments) shall determinn the need for Jnspection based on the following.

3.1.1  !

Classification of the component (Reference 5.1.8).

3.1.2 The use of Appendix A.

i 3.2 Identification  !

The preparer shall identify and include in the instructions, procedures, eqi3 or other work documents, the inspection requirements as defined by this procedure, t_;;)

3.2.1 Appendix A describes how the inspection points are to be identified and what information is required for proper identification.

3,2.2 The Quality Control Department shall review the work document to ensure that the appropriate inspection requiremencs have been established in accordance with Appendix A and may add Inspection Points as necessary.

3.3 Planninn Requirements Quality inspection planning shall include provisions for the following:

3.3.1 Identification of applicable instructions, procedures, design drcvings, and specifications. -

3.3.2 Identification of the characteristics, attributes, and activities to be inspected.

5.3.3 Identificatien of the organization responsible for performing the inspections, if other than ANPP QC.

4

~~>

PV216-DRA 144,i p- -

DOC. NO: QA02.02 ,

REVISION: 2 PAGE 4 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS

~

3.3.4 Qualitative / Quantitative Inspection Acceptance Criteria (via Drawing, specification, code, standard, instruction or Procedure) are provided in the work step or clearly Referenced in the work step. References or supporting documentation not germane to the inspection will not be included in the Inspection Acceptance Criteria.

NOTE: Ambiguous terms such as " sufficient, adequate, proper, ample, suitable" shall not be used when inspections are required.

3.3.5 Identification of the special mcastring and test equipment requirements.

3.3.6 Provisfons for the inspector to document acceptance or rejection of the inspection in accordance with paragraph 3.8 of this Procedure. This may be in an appendix to the work documer .

as shown in Appendix B.

3.4 Work Documents The instructions, procedures, or other documents prepared to perform construction, maintenance, modification, testing or other work / activities shall incorporate the inspection planning requirements of paragraph 3.3 of this Procedure.

3.5 Performance 3.5.1 Work orders that require changes after approval shall meet the requirements of Work Control 30AC-9ZZ01.

3.5.2 Hold Points and Witness Points contained in approved procedures may only be changed by formal change of that document (i.e.,

PCN, TPCN).

3.5.3 Inspection Points that are not applicable, because the associated work step was not performed shall be marked N/A in the work document by the performer.

3.5.4 Inspection Points or attributes within the inspection that cre not required for the worn being performed may be deleted and the reason for the deletion annotated in th' Nork Documer.r.

PV2ilfAA 1844)

/2IIt DOC. NO: QA02.02 SUff' REVISION: 2 PACE 5 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS 3.5.5 If during the process of inspection, Quality Control determines that Hold or Witness Points other than those originally specified are necessary, Quality Control may identify the inspection point provided they follow the requirements of Appendix A and paragraph 3.5.2.

3.5.6 Only the Manager of Quality Control, QC Supervisor, or a designee (the designee must be designated in writing) are authorized to waive QC Holdpoints. Holdpoints may be waived only under certain conditions such as high radiation (ALARA),

and then only if adequate process documentation exists to assure the quality requirements have been met. When Inspection Holdpoints are waived, che authorizing individual shall sign and date the affected document indicating the holdpoint has been valved and the reason for the waiver.

g(!g 3.5.7 Quality Control Holdpoints within work orders may be changed to ifiy Quality Control Witness Points when allowed by this procedure (Appendix A).

3.5.8 The Quality Control Inspector shall verify all acceptance criteria specified for the identified attributes.

3.6 jten-Conformance 3.6.1 Non-conforming conditions, identified by Quality Control during the performance of inspection, shall be documented using an Engineering Evaluation Request (EER) or a Work Request (WR).

3.6.2 When non-conformanme documents (i.e., EER, or VR) are initiated by Quality Control, the non-conformance document number shall be entered in the Work Document.

3.6.3 If work proceeds past a QC Hcid Point without being inspected or waived in accordance with this procedure, the inspector shall generate a monitoring report to document the procedural violation. The QC inspector shall perform the inspection if possible and reference the monitoring report number in the work document. If the inspection cannot be performed, the QC inspector shall generate en EER document or ensure the work order is amended to re-perform the work and inspection.

d
  1. Y21%)e A 1844)

~'

DOC. NO: QA02.02 REVISION: 2 PAGE 6 OF 50 DATE: 06/21/88 Arizona Nuclear Power Proj ect TITLE: QUALITY CONTROL INSPECTIONS 3.7 Personnel Qualifications 3.7.1 Quality Control Department Personnel shall be qualified in t.ccordance with QA02.01 prior to performing, documenting, or evaluating any inspections.

3.7.2 Contractor personnel shall be qualified and certified in accordance with OA02.01 or their own ANPP Approved Qualificacion/ Certification Program prior to performing, documenting, or evaluating any inspections.

3.8 Documentation NOTE: The following directions are applicable unless delineated in other procedures.

3.8.1 Completed inspection points shall be .igned, initialed or -

stamped and dated by the responsible inspector. The responsible inspector shall' indicate acceptability of an '

inspection as " Acceptable" or " Unacceptable".

NOTE: Inspection points shall not be signed, initialed or stamped prior to the completion of the entire inspection.

t 3.8.2 Inspection points which .. ve- been " partially" inspected shall be noted in the work document at the completion of the

" partial". The partial inspections should be described as concisely and accurately as possible for the attributes inspected. When practical, " partial" inspections should be annotated at the inspection point. If the " partial" inspection attributes must be noted .isewhere in the work document (i.e.,

Work Continuation Sbc oc, Gene.-ic Hnidpoint Forms) it should be s so noted at the inspection poiv . Noted partial inspections require signature, initials or stamp and date by the responsible inspector.

y __ _ _ ___

l l-gy"[}. DOC. NO: QA02.02 s;A REVISION: 2 PAGE 7 OF 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS 4.0 DEFINITIONS AND ABBREVIATIONS 4.1 Definitions 4.1.1 Hold Point -

An in process or final inspection point for which which QC must be notified prior to the operation, so that an inspection can be performed. Worx shall not proceed past the hold point until the inspection is complete or vaived and the

., work dceument properly anz. stated.

4.1.2 Quality Control Inspector - A member of the ANPP Quality Control Department who is qualified and certified in accordance with reference 5.1.2.

4.1.3 Vork - Any activity (i.e., mainte*ance, modification, testing, inspection or examination) that at any time during its 6333 performance changes permanent plant equipment or components to 639 a configuration in disagreement with the design documents.

This includes removal, replacement, disassembly, assembly, reassembly, or installation of any permanent plant component.

Any specific requirement stated in the body of a test Procedure which will cause a permanent plant component to be in configuration that does not agree with the design documents.

4.1.4 Witness Point - An in-process or final Inspection Point for which QC must be notified prior to performing the work so that an inspection may be performed. Work may proceed past a Witness Point if the QC inspector is not present.

4.2 Abbreviations 4.2.1 AIARA - As Low As Reasonably Achievs .',e 4.2.2 EER -

Engineering Evaluation Rcqu.*

4.2.3 N/A -

Not Applicable 4.2.4 PRB -

Plant Review Board 4.2.5 g -

Circle Q Symbol for Quality Control Hold Point 4.2.6 OC -

Quality Control

_ " ;l 1

4.2.7 W/P -

QC Witness Point 4.2.8 UR -

Work Recuest PV2164MA (444)

l l

+ l DOC. NO: QA02.02 REVISION: 2 PAGE S OF 50 DATE: 06/21/88 Arizona Nuclear Power Projact TIT 1.E: QUALITY CONTROL INSPECTIONS

5.0 REFERENCES

5.1 Implementing.

5.1.1 30AC-9ZZO4, " Housekeeping" 5.1.2 QA02.01, " Qualification and Certification of Inspection Personnel" 5.1.3 73AC-9ZZ07, " Control of Approved Materials for Nuclear Compatibility" 5.1.4 30AC-92Z01, " Work Control" 5.1.5 73AC-0ZZ29, " Engineering Evaluation Request" 5.1.6 EX01.03, "ANPP Administrative Policies and Procedure Control '"

Manual" 5.1.7 7BAC-OZZ01, " Nuclear Operation Docum..nt and Manual Control" 5.1.8 ES03.02, " Quality Classificatior of Structures, Systems and Components" 5.1.9 73AC-9ZZ05, " Temporary Modification Control" 5.2 Developmental 5.2.1 30AC-92201, " Work Control".

5.2.2 ANSI N4b.2.9, 1974, "Roquirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants" -

5.2.3 ANSI N18.7, 1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plant" 5.2.4 Palo Verde Nuclear Generating Station Final Safety Analysis Report, amendment 14 5.2.5 ES03.02, " Quality Classification for Structures, Systems, Components, Spare Parts and Activities".

mi ma im

.~.

13. n DOC. NO: QA02.02 REVISICN: 2 PAGE 9 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS 6.2.6 Cuideline INPO E4 003, " Guidelines for Quality Control Inspectors and Non-Destructive Examination Technicians

. Training" 5.2.7 ANSI N45.2.1, 1973, " Cleaning of Fluid Systems and Associated Components of Nuclear Power Plants" 5.2.8 ANSI N45.2.2, 1972,

  • Packaging, Shipping, Receiving, Storace, and Handling of Items for Nuclear Power Plants ' '

5.2.9 ANSI N45.2.3, 1973, " Housekeeping During the Construction Phase of Nuclear Power Plants" 5.2.10 ANSI N45.2.4, 1972, " Installation, Inspection, Testing '

Requirements for Instrumentation and Electric Equipment",

p,3/4 5.2.11 ANSI N45.2.5, 1974, " Installation, Inspection and Testing of cf Structural Concrete and Structural Steel".  !

5.2.12 ANSI N45.2.6, 1978, " Qualification of Inspection, Examination and Testing Personnel for Nuclear Power Plants"  !

5.2.13 ANSI N45.2.8, 1975, " Installation, Inspection and Testing of Mechanical Equipment and Systems".

5.2.14 ANS 3.1, 1978, "American, National Standard for Selection and Training of Nuclear Power Plant Perscnnel" 6.0 Appendices 6,1 Appendix A, Identificttion of Hold. Points and Witness Points a

6.2 Appendix B, Inspection Point Release Form 3',

w :t%

I m,wnw,

pp3g

.O.t

'^

DOC. NO: QA02.02 REVISION: 2 PAGE 10 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 1 of 40

1.0 Purpose and Scope

1.1 Provides instructions for determiring inspection points required to be identified within quality-related work orders and procedures that identify work to be performed.

2.0 Definitions and Abbreviations 2.1 See paragraphs 4.0 of this Procedure.

2.0 Application of Inspection Points 3.1 General Instructions

-%g

{$y, 3.1.1 Required Inspection Points have been derivad from those quality related activitier identified in FSAR, implementing Regulatory Guides, specifications and Regulatory Commitments.

3.1.2 Type of inspection point assigned (either HOLD POINTS or WITNESS POINTS) shall be identified at the work step.

3.1.3 Hold points shall be used for safety-related equipment, structures or components as-identified in this appendin, unless the work document is a Preventive Maintenance (FM) work order, in which case hold points shall be used in accordance with sections 4.1.1, 4.1.2, 4.1.3, 4.1.4 and 4.1.6 of this appendix.

All other safety-related FM inspections may be witness points.

3.1.3.1 Inspection Points are not required for troubleshooting and/or test work packages shen inspections attributes are not affected.

3.1.4 Witness points may be used for all equipe.ent classified as important to safety (ITS) unless conflict exists between this procedure and other approved documents (i.e., procedures, specifications, drawings, vendor requirement) in which case a hold point shall be used.

d

I DOC. NO: QA02.02 REVISION: 2 PACE 11 0F SO DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL IN3PECTIONS

{

l l

Appendix A l

. Page 2 of 40 3.1.5 Additional inspection poit,ts may be identified as necessary by planners, work group supervisors, or QC based on the importance I of the activity, disposition of an EER, or based on data that ident'.ttes areas that may require more attention to ensure the activity is assembled, installed or performed ccrrectly.

3.1.6 Within this appendix inspection attributes are listed folloving the inspection topic. The applicable attributes shall be identifiable within the work step (s), referenced at the work step (s), or within the inspection point. All applicable attributes shall have inspectable acceptance criteria identified or referenced. References or supporting documentation not germane to the inspection shall not be included in the Inspection acceptance criteria. (NRC c-Information File 88-056-26) .

3.2 The following are recommended methods for identifying inspection points within work documents.

. 3.2.1 Example for Hold Points.

QC HOLD POINT: Work shall not proceed without inspection being performed and identified as acceptable or the non-conformance document identified.

Work description with identifiable attributes and acceptance criteria for an activity where a hold point is required.

Identification of attributes to be inspected if verification of the complete step is not required to be inspected.

QC Stamp OC Stamp Acceptance / Date Unacceptable / Document Number / Date

~

mw iew

rila DOC. NO: QA02.02

'.h REVISION: 2 PAGE 12 0F 50 DATE: 06/21/88 Arizona Nuclear Power PrcJect TITLE: QUALITYCONTROLI?IPECTIONS Appendix A Page 3 of 40 3.2.2 Examp.e of Witness Hold Points.

QC WITNESS Quality Control must be notified prior to performing POINT: this activity. If the inspector is not availabic (i lI work may proceed. l l

QC notified I WGS / Date l

Work description with identifiable attributes and acceptance criteria for an activity where witness points may be used, i

-gd T' -

Identification of attributes to be inspected if

' verificating of the complete ~

oat r,equired to be inspecrec.

QC Stamp OC Stamp tiUMBER DATE Acceptance / Date Unacceptabla / Dccument Number / Date 3.2.2.1 When inspection of witness points are not performed, the witness point -inspection spaces may be lef' blank within th. work document or as identified in o:hcr procedures.

3.2.3 When calibrated tools are used to perform inspections, space shall be provided for the inspector to identify M&TE used, expiration date, and the actual value(s) identified.

EXAMPLE: (2/31/99)

(MM-105) 250 ft. lbs.

SERIAL NUMBER DUE DATE VALUE (50 to 250 rance idenrified on sticker)

COMMENTS

(*)

STAMP / DATE

, ') (*) QC stamp / initials signifies that the equipment used is within any restrictions identified, and the information recorded is correct.

~

evve** m

D00. NO: QA02.02 REVISION: 2 PAGE 13 OF $0 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUAI.ITY CONN 0L INSPECTIONS Appendix A Page 4 of 40

').2.4 When ASME pressure retaining (over 1 inch), NF, MC parts / components are installed and during 3,pplication of quality-related coatings. Space shall be provided for the inspector to identify heat / serial / batch number installed or used.

EXAMPLE:

(XX) -

C6I NUMBER llEAT/ SERIAL /BATCl! STAMP /DATE (YX) QC stamp signifies information recorded is correct.

3.2.5 Contractor procedures that do r.ot have inspection points identified within the body shall have a circle (Q) or circle (WP) identified in the left margin of a work step. (Q) signifies a hold point and (WP) signifies a witness point. '

When these codes are used, a form similar to Appendix B shall be used to identify the attributes to be inspected and the acceptable / unacceptable status of the tuspection. This form shall be identified as a work order attachment.

O PY71WA ($ 44l

men.>

h24 w* DOC, NO: QA02.02 REVISION: 2 PACE 14 0F $0 DA' : 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INS!'ECTIONS Appendix A Page 5 of 40 IN02X OF INSPECTION POINTS Appendix A SECTION TIT 1.E PAGE ?RPIBER 4.0 INSPECTION POINTS 4.1 CENERAL INSPECTION POINTS 4.1.1  !!ou,ckeeping 7 4.1.2 Internal Cleanness 8 4.1.3 Foreign Material Exclusion (FME) 9  !

4.1.4 Tightness of Connections and Fasteners 10  ;

4.1.5 Dimensional Inspection 11 4.1.6 Correct Material l 11 4.1.7

[7% Rigging 12  !

s hv 4.1.8 Chemical Cleaning 14 l 4.2 MECllANICAL INSPECTION POINTS 4.2.1 Equipment /Part Installation 15 4.2.2 Pipe liending 15 4.2.3 Comnonent Supports 16 4.2.4 Pump Rework / Repair 17 4.2.5 Drive coupling Alignment 17 4.2.6 Pipe Installat,on/R' d1' un 18 4.2.7 IIVAC 19 4.2.8 Valve Re' ark / Rep ,

19 4.2.9 PSV Testing and I tetir.r. 20 4.2.10 Prensure Test.in" 20 4.3 ELECTRICAL INSPECTION 'O. Ti 4.3.1 Equipmerw/Pa r- Ir allorion 21 4.3.2 Solde*'tg 21 4.3.3 lien Trim 22 4.3.4 Compot. .c Supports (Raceway, Condult) 22 4.3.5 Termina'*.ons 23 4.3.6 Cable /Vire Installation /Reinsta11ation 23 4.3.7 Raceway Inst.allation/ Reinstallation 24 4.3.8 Limit Switch Settings 24 4.3.9 Auxiliary Relays / Cabinets 24 4.3.10 Electrical Tests

) 25 m,-..,

~

DOC. NO: QA02.02 REVISION: 2 PAGE 15 OF 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 6 of 40 SECTION Appendix A TITLE PACE NUMBER 4.4 INSTRUMENTATION INSPECTION POINTS 4.4.1 Instrument / Equipment /Part Installation / Reinstallation 25 4.4.2 Tube Installation 26 4.4.3 Flex Hose Installation / Reinstallation 26 4.4.4 Tube / Component Supports 27 4.4.5 Terminations 27 4.4.6 Cable / Wire Installation / Reinstallation 28 4.4.7 Soldering 28 4.4.8 Heat Shrink 29 4.4.9 Pressure Testing 29 <?

4.5 SPECIAL PROCESS E DECTION POINTS 4.5.1 Heat Treatment 30 4.5.2 Pipe Weldina 30 4.5.3 Structural Welding 31 4.5.4 Hardsurfacing 32 4.5.5 Tube Plug Welding 33 4.5.6 Brazing 33 4.5.7 hase Metal Repair 34 4.5.8 Weld Repair 35 4.6 CIVIL INSPECTION POINTS 4.6.1 Anchor Bolts 36 4.6.2 Coating 36 4.6.3 Concrete and Masonry Drilling 36 4.6.4 Cadweld Splicing 37 4.6.5 Reinforcing Steel 37 4.6.6 Structural Steel 27 4.6.7 Crouting 38 4.6.8 Concrete 38 4.6.9 Fireproofing 39 4.6.10 Soils 40

-.. l

  • p __

S$.M DOC. NO: QA02.02 REVISION: 2 PAGE 16 OF 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL 4ASPECTIONS Appendix A Page 7 of 40 4.0 Inspection Points 4.1 General Inspection Points Inspection points are identified as follows along with attributes that may be applied where applicabic to the inspection.

The acceptance criteria to be identified / referenced within the work document is for the individuals performing the work and QC inspection.

4.1.1 Housekeepinn Inspections Zones I, II and III

. Required QC HOLD POINTS for safety related systems ,

Required QC VITNESS POINTS for ITS systems v_.

Attributes: / Prior to 'one Implementation)

A. Area posted and boundaries establ.shed.

B. Area procleaned to Zone requirements.

C.

Logs established for controlling personnel access and material / tool accountability.

Attributes: (Prior to Zone Closure)

Required QC HOLD POINTS for safety related s, sten; Required QC WITNESS POINTS for ITS systems D.

Log reconciled to assure all materials are accounted for.

E.

Area re-established to new requirements, l

'"Q I

x ' i

.l i

evv m >i m i l

DOC. NO: QA02.02 t.

REVISION: 2 PACE 1.7 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 8 of 40 4.1.2 Internal cicanner.s The following items DO NOT require QC inspection for cleanness or (FME).

1. -

Instrument lines 3/8" dia, and less provided lines / components are capped immediately upon removal, uncapped and reconnected to the correct fitting / location upon completion.

2.

Vent and drain lines downstream of isolation valves.

(This is NOT exempt if lines cre to be attached and fluids are to be returned to the system.)

/~

3. Routine addition of oil or drainir.g and refilling oil rese rvoirs .

4 Valve and pump stuffing boxes.

Required QC HOLD POINIS for safety related systems Required QC UITNESS POINTS for ITS systems

1. New installation of all piping / tubing lines and piping components /equioment.
2. Re-establishing cicanliness of repaired / reworked parts and components.
3. Prior to connecting (T-MODS) temporary piping / test connections to permanent piping if flow is into the system.

4 Final flushing for cleanliness verification of systems or temporary lines used to input fluics into a system.

Attributes:

A. Required cleanliness level achieved

B. Method of cleaning C. haterials to be used for cleaning process are on the _

AML.

esm-au ,se -

f;T..

C DOC. NO: QA02.02 REVISION: 2 PACE 18 0F 50 DATE: 06/21/88

t. -

Arizona Nuclear Power Project TITLE: QUALIIT CONTROL INSPECTIONS Appendix A Page 9 of 40 4.1.3 Foreign Material Exclusion (FME)

REQUIRED QC HOLD POINTS for safety-related systems.

Required QC Witness Points for ITS systems.

4.1.3.1 DIE Inspection Points shall be established to prevent degradation of cleanness for installed systems or components whic). may become contaminated due to associated work activities.

NOTE: (see paragraph 4.1.2, 1,2,3 & 4) 4.1.3.2 Temporary closure device should be used whenever Q posrible.

{p-f! ' If the use of a closure device is not practical, Housekeepin5 Zones I, II or III should be ,

established to prevent degradation of the systems.

s 4.1.3.3 System connections may be loosened to facilitate draining the system prior to first fliE inspection.

The system is considered breached when the internal system is visually accessible.

Attributes: (Prior to breaching the system)

A. Area / Component precleaned to prevent system from being contaminated during opening of the system.

(During.the breaching of system / equipment)

3. Foreign material excluded during breach of the system, (verified until closure devices are installed).

C. Temporary closure device installed and its installation documented.

Q -

D. Tools / Device made fail safe (e.g., tethered) when closure devices not used.

PV21&C6A (06.4; I

\

_ _ . _ _ _ _ - - - - - - - - - " - - - - - - - - - - - ' - ^ - - ' - - - - ' - ' _ _ _ , _ _

_ . __ - - - - - - - - - - - - - - - - - - " " ~ ^ ' ' ^ ^ - ~ ^ ^ - ~ ~ ~ - '

s DOC.-NO: QA02.02 N1 REVISION: PAGE 19 0F $0 DATE: 06/21/88 Arizona Nuclear Power Project - '

. TITLE: QUALITY CONTROL INSPECTIONS

~

Appendix A-Page 10 of 40 (Post work; prior to system closure)

E. Foreign material excluded from the system or component (verified until closed).

s; F. - Closure device removed and its removal documented.

G. Internal cleanness for reworked, repaired or new components (see paragraph 4.1.2 for attributes).

4.1.4 Tightness of Connection and Fasteners f-].

a 1.z v:

REQUIRED QC HOLD POINTS for:

1. Safety-related pressure boundary connections.

2.- Seismic category 1 mounting bolts.

3. . Safety related equipment assembly. Internal bolting when required.

4 All ASME pipe supports.

. Required Witness Points for ITS system pressure boundary connections at.d Seismic category 9 mounting bolts.

t Attributes: -

A. Correct material (see paragraph 4.1.6)

'B .

Cleanness and damage of thread and bearing mating / sealing surfaces.

C. Lubricants (type, on the AML).

D. Torque sequence and final torque.

.E. Thread engagement.

Pv?'64A 14441 -

, _ . - - . . . _ _ - . . . _ ~ _._._ _. . , . - . . _ _ . ..- ,

g7g

- DOC. NO: QA02.02 REVISION: 2 PACE 20 OF 30 DATE: 06/21/88 Arizona Nuclear Power Projact TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 11 of 40 4.1.5 Dimergtonal Inspection QC HOLD PoltiTS/ Witness Points are not required unless identified by engineerin5. Planner, drawing, specification, or procedure.

Attributes:

A. Confirm calibration of inrpection tools, E. Surface condition if required.

C. Verify dimensions within tolerance.

Additional Attributes for material machined or f abricated:

!h)

D.

Correct material, prior to cutting from original stock (see paragraph 4.1.6 for attributes).

E. Parts properly identified / marked.

F. Final cleanness of parts (see section 4.1.2 for attributes).

4.1.6 Correct Material REQUIRED QC HOLD POINTS for Safety-Related Required Witness Points for ITS 4.1.6.1 Correct Material Verification is not necessary for parts identified in "SPAREX" as non-quality related.

4.1.6.2 QC Witness / Hold Point inspection for correct caterial shall always include verification of the part/ccmponent identification by the applicable attributes listed below for each item installed, or a Bill of Materials Sign-off for multiple installations.

PV216@l A (44b4)

DOC. NO: QA02.02 REVISION: 2 .

PACE 21 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix C Page 12 of 40 Attributes:

A. Documentation using Class and Item Numbers for material verification, or other acceptance criteria that will identify the component to requirements when class and item numbers are not available.

NOTE: When ASME pressure retaining (over 1 inch),

NF, MC parts / components are installed and during application of quality-related coatings, the QC Inspector shall document the heat /seris1/ batch number within the work document. . - .

f.

Observation of the Instal:ation (see applicable section for identification of installa-ion attributes).

4.1.7 Ringint NOTE: See Rigging Manual for identification of definitions and clarification within this section.

NOTE: Special Liftin6 Device - A lifting device for handling loads over 2000 lbs. in the proximity of irradiated fuel or safe shutdown equipeent for which the use of simple slings is not appropriate.

4 1

((k) wu DOC. NO: QA02.02 REVISION: 2 PAGE 22 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 13 of 40 4.1.7.1 Testinn of rinninn REQUIRED QC HOLD POINTS for tes::ing of SPECIAL LIFIING DEVICES (QC is not required for other lifting devices).

Attributes for Special lifting devices:

A.

Load test amount or identification of couipment PO number. If load test is required:

Ayl,

1. Pre-visual inspection
2. Test weight (documentation) 56_/ 7 Test time
4. Post-visual inspection B. Identification tag or number etched on component.

4.1.7.2 Fabrication of rinninn equipment REQUIRED QC HOLD POINTS for SPECIAL LIFTINC DEVICES Attributes:

A. Welding (see section 4.5)

3. Load rest (see paragraph 4.1.7.1) a 1

PV21W A 1844)

I DOC. NO: QA02.02 REVISION: 2 PACE 23 0F $0 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 14 of 40 4.1.7.3 Rinning of components REQUIRED QC HOLD POINTS for che use of SPECIAL LIFTT*1C DEVICES, and when other lifts are over 2000lbs performed in safety related areas.

Required QC Vitness Points when rigging other safety.

related components.

Attributes: (pre-lift)

A. Identifict. tion (required on all rigging parts) with rated capacity B. Rigging attachment (Rigging Manual or wu Approved Drawings)

1. method of attachment and sling orientation
2. center of gravity / balance point
3. tag lines if identified in instructions 4 load path (walk down) 4.1.8 Chemical Cleaning REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Vitness Points for ITS systems Attributes:

A. Type cleaning B. Solvent type C. Final cleaning solvent D. Compatibility (AML)

E. Temperatures F. Soak times G. Safety precautions H. Final cleaning (rinse) (see paragraph 4.1.2)

Pv7t&onA st443

f; O O 9

w~

v

': ~', '

IMAGE EVALUATION '%

N \//gf Cg/ TEST TARGET (MT-3)

/ I

'4

\//,/ p

+

,,f$1 l.0  : ".

y i

1.1

^

S Fli! l.8 lli!l*am I.25 i 1.4 l!l I.6 i l it !==

4 150mm >

4 6 --->

hf fl

$? I'&,, .+

' f

/4%

4y~ )jj>77,y,,,

////h' 3  ?;g

e;,aA IMAGE EVAL.U ATION 1 ,/// a, O .

g

/// '

$f TEST iARGET (MT-3) '\/ g,

\ si /[ (;

a :s I,o v

l,l ddS lML l 125_ i.4 m i.6 c-- .

4- - 150mm >

6" >

i

/ ,;

%y/,/ , ,, /+

4%

////h O

ge 17

,gy

. - _ - - _ - _ _ _ _ - . - _ _ - - - _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ = _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __-

Q 4 g

'L'N,.

IMAGE EVAL.UATION /\ / i g

g Y//

TEST TARGET (MT-3)

\\// j \ s 4> y 1.0

2.2 l,l _

jl4 1.8 n=

1.25  ! l.4 i 1.6 i

y ==

150mm -->

< 6" >

l nJb

%, +.k 4 m g ,g.,pp <

._ : - k

' ^

xxxx4%

6 cb 9-l

@ 0 DOC. NO: QA02.02 REVISION: 2 PAGE 24 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITII: QUALITY CONTROL INSPECTIONS Appendix A Page 15 of 40 4.2 Mechanical Inspection Points 4.2.1 Equipment /Part Installation / Reinstallation REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Vitness Points for ITS systems Attributes:

A. Correct material (see paragraph 4.1.6)

B. Cleanness (see paragraph 4.1.2)

C. Location and orientation per design De Leveling and alignment per design a3 E. Clearances and tolerances per design f ' F. Tightness of connections (see paragraph 4.1.4)

G. Lubricants (type, on AML)

H. Condition of mating surfaces I. For welded equipment (see section 4.5)

J. Rigging (see paragraph 4.1.7.3) 4.2.2 Pipe Bending REQUIRED QC HOLD POINT for Safety Related piping Required QC Witness Point for ITS piping Attributes: (before bending)

A. Correct material (see paragraph 4.1.6)

B. Outside diameter -

C. Wall thickness D. Pre-heat (if applicable)

Attributes: (after bending)

E.

Outside diameter (out of roundness)

F. Wall thickness G. Bend radius

^ H. Defects (cracks, wrinkles)

_ I. Post cleaning J. Post-heat treatment (see paragraph 4.5.1)

PVJ16-08A 15-44)

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ _ _ - - - _- - - - _ - - - - - - - - - - - - - - - - - - ------- -~~~- ~

i DOC. NO: QA02.02 REVISION: 2 PAGE 25 0F SO DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 16 of 40 4.2.3 Component Supports (Restraints, hangers, snubbers)

Attributes:

A. Configuration / location / orientation per design B. - Clearance and tolerance per design C. Level and alignment per design D. Correct material (see paragraph 4.1.6)

E. Locking devices installation.

F. 'w' eld inspection (see section 4.5)

G. Anchor bolts (see paragraph 4.6.1)

H. Clamps U-bolts:

1. clamp snug on pipe
2. Bolts / nuts tightened (sea paragraph 4.1.4) "
3. lock device, if required, installed .

NOTE: "*" REQUIRED attributc for .=afety-related systems.

Beam attachment / load pin sire and installation, per the appropriate vendor manual. This requirement is from CAT report #50-530/86-03.

I. Variable spring

1. Travel stop removed, stored properly
2. Cold setting / hot setting
3. Tightness of connections (paragraph 4.1.4)
  • 4. Beam attachment / load pin installation J. Constant support
1. Same as variable spring R. Snubbers (for Section IX Inspection, see 73ST-92221)
1. Proper model (see paragraph 4.1.6)
2. Verify stroke
3. Pin to Pin dimension 4 Angle of attach =ent
5. Shipping plugs removed if required
6. Evidence of leaks
7. Cold / hot piston settings
8. Reservoir orientation / fluid level j 9. Piston rod damage
10. Pin installation with snap rings l 11. Staking of spherical bearing (Reference EER evmaa ,m 87-XM-006)

[{Eh DOC. NO: QA02.02 9:.' .

REVISION: 2 PACE 26 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 17 of 40 4.2.4 Pump Rework / Repair REQUIRED QC HOLD POINT for Safety-Related equipment Required QC Witness Point for ITS equipment Attributes:

A. Housekeeping Zone (see paragraph 4.1.1) OR B. FME during pump disassembly (see paragraph 4.1.3)

C. Dimensional inspection when required by design (see paragraph 4.1.5):

1, wear rings

2. impeller e5
3. shaf t j ournals

(.I '

, 4. seals D. Correct material (see paragraph 4.1.6)

E. Internal cleanness (see paragraph 4.1.2)

F. Tightness of connections (see paragraph 4.1.4)

G. FME during reinstcl'.ation (see paragraph 4.1.3)

H. Component support reinstallation (see paragraph 4.2.3)

I. Drive coupling alignment (see paragraph 4.2.5) 4.2.5 Drive Coupline Alignment (Preliminary and final)

REQUIRED QC HOLD POINT for Safety-Related Required QC Witness Points for ITS l Attributes: -

i A. Type (cold, hot)

B. Cold differential / equipment temperature C. Tightness of connections (mounting bolts) (see paragraph 4.1.4) l D. Piping reconnected (see paragraph 4.2.6) l E. Cold spring (see paragraph 4.2.6) l -F. Alignment tolerance (parallel, angular and coupling

,3 gap)

_' G. Soft Foot 1

[ n:n- ...

l t

~ ,

DOC. NO: QA02.02 REVISION: 2  :

PAGE 27 0F 50 DATE: 06/21/88 {

Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 18 of 40 4.2.6 Pipe Installation / Reinstallation REQUIRED QC HOLD POINT for Safety-Related Required QC Witness Points for ITS Attributes :

l A. Correct material (see paragraph 4.1.6)

B. Internal cleanness (see paragraph 4.1.2)

NOTE: During activity all open end portions cust be maintained with FME closures for clean systems and co=ponents (see paragraph 4.1.3).

C.

Location and orientation per design

1. flow direction (valves, orifices)

D. Leveling and alignment per design

1. pipe slepe maintained E.

Clearances and tolerances per design F.

Tightness of connections (see paragraph 4.1.4)

C. Welding (see section 4.5)

H. Pipe strain I.

Pipe bending (see paragraph 4.2.2)

J.

Asbuilt verification for new installations and changes to design PV7HHM A (a%

-a

A

?!?! DOC. NO: QA02.02 REVISION: 2 PAGE 28 0F 50 DATE: 06/21/ss Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 19 of 40 4.2.7 HVAC REQUIRED QC HOLD POINTS for Safety-Related Required QC Witness Points for ITS Attributes:

! A. Correct material (see paragraph 4.1.6)

B. Internal cleanliness (see paragraph 4.1.2)

C.

Location and orientation per design D. Clearances and tolerances per derign E. Tightness of connections (see paragraph 4.1.4)

1. One time use of whi: nuts n

~ *("' ,

F. Welding (see section 4.5)

C. FME (see paragraph 4.1.3) 4.2.8 Valve Rework / Repair REQUIRED QC HOLD POINT for Safety-Related Required QC Witness Points fo- ITS Attributes:

A. FME during disassembly (see paragraph 4.1.3)

B.

Dimensional inspection (see paragraph 4.1.5)

C. Correct material (see paragraph 4.1.6)

D. Internal cleanness (see paragraph 4.1.2)

E.

F.

Tightness of connections (see paragraph 4.1.4)

Blue check (if performed) -

C.

Location and orientation per design PV71WA 444)  !

DOC. NO: QA02.02 REVISION: 2 N PACE 29 0F 50 DATE: 06/21/38 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 20 of 40 4.2.9 PSV Testing and Setting REQUIRED QC HOLD POINT for Safety-Related systems Required QC Vitness Points for ITS Attributes:

A. FME (see paragraph 4.1.3)

B. Cleanness of test apparatus (see paragraph 4.1.2)

C. Correct test medium D. Calibration of testing device E. Pressure temperature calculations F. Verification of test / final setting readings C. Installation of anti-tamper devices

H. System restoration (for inservice testing only) s ,

4,2.10 Pressure Testing (excluding ILRT, LLRT or those pressure test

.pylicable to ASME Section XI 73TI92213)

REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Witness Points for ITS Attributes:

A. System walkdown to design documents B. M&TE verification, range requiremente C. Appropriate pressures, temperatures D. Water chemistry (when applicable)

E. Bubble solution (when applicable)

F. Time at test pressure -

C. Visual / Bubble inspection / test results H. Instrumentation and items external to test boundary are isolated during testing I. Overpressuricetion protection J. Caging and ungaging of relief valves R. Supports have hydrostatic pins installed and removed where applicable (see paragraph 4.2.3)

L. Post-test cleanliness i

- 1

~2...,

([7h DOC. NO: QA02.02

% ~

REVISION: 2 PAGE 30 OP 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 21 of 40 4.3 Electrical Inspection Points 4.3.1 Eculpment/Part Ins talla tion /Re ins talla tion REQUIRED Q0 HOLD POINT for Safety-Related systems Required QC Witness Points for ITS Attributes:

A. Correct material (see paragraph 4.1.6)

B. Location and orientation per design C. Leveling and alignment per design D. Clearances and tolerances per design g??, E. Tightness of connections (see paragtaph 4.1.4)

~ '

F. Lubricants (type, on AML)

G. Condition of mating surfaces H. Ri SSi ng (see paragraph 4.1.7)

I. Leak rate test (electrical penetrations)

J. Nitrogen purge (electrical penetrations) 4.3.2 Soldering REQUIRED QC HOLD POINTS for Safety Related systems Required QC Witness Points for ITS systems Attributes: (prior to soldering)

A. Correct solder material (type)

B. Correct cleaning material (type)

C. Correct soldering equipment (rating, heat sinks)

D. Cleanness (area, material)

Attributes: (during soldering)

E. Per site / vendor requirements F. Heatsinks in place

/. ~

Attributes: (after soldering) b(j C. Final visual PY2 4WI A 1644)

1 D0C. NO: QA02.02 REVISION: 2 PAGE 31 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 22 of 40 4.3.3 }{ cat Shrink REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Vitness Points for ITS systems Attributes:

A. Correct material (see paragraph 4.1.6) (correct Kit)

B. Tet_" nation (see paragraph termination 4.3.5)

C. Cable /vire preparation D. Shims installed E. Final visual 4.3.4 Component Supports (Racevav, Conduit) ' ' '

REQUIRED QC HOLD POINT for Safety-Related supports Required QC Witness Points for ITS supports Attributes:

'A. Configuration / location / orientation per design B. Clearance and tolerance per design C. Level and alignment per design D. Correct material (see paragraph 4.1.6)

E. Locking devices installation.

F. Weld inspection (see section 4.5)

C. Anchor bolts (see paragraph 4.6.1)

H. Clamps installed

1. Bolts / nuts tightened (see paragraph 4.1.4)
2. lock device, if required, installed eva.ua i..,

l 1

.([5)

'l DOC. NO: QA02.02 REVISION: 2 PAGE 32 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 23 of 40 e

4.3.5 Terminations REQUIRED QC HOLD POINT for Safety-Related supports Required QC Vitness Points for ITS supports Attributes:

A. Correct material (._e paragraph 4.1.6) '

B. Termination tool C. Termination landing points D. Separation criteria E. Training / bend radius F. Identification (marking on wire / cable) {

zyg G.

Tightness of connection (see paragraph 4.1.4) l 3 '.y. H.  !

Cable / conductor prep (stripping and cutting)

I. Vire penetration (e.g., into lug /cennector/ splice)

J.

K.

Heat shrink installation (see paragraph 4.3.3)

Soldering (see paragraph 4.3.2)

L. Final visual M.

N. Flex conduit (reinstallation /instcllation)

Termination support 4.3.6 Cable /Vire Ins talla tion / Reins ta11a ti on REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Vitness Points for ITS systems Attributes:

A. Correct material (see paragraph 4 1.6)-

B. Routing C. Separation criteria D. Raceway preparation E. Pulling preparation F. Lubrication C. Cable pull tags H. Reel number r ~

I. Cable end cap sealed J. Bend radius K. Cable ties misa. iew

DOC. NO: QA02.02 i[

REVISION: 2 PAGE 33 0F 50 DATE: 06/21/88

. Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 24 of 40 4.3.7 Racevav Installation / Reinstallation REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Vitness Points for ITS systems Attributes:

A. Correct material (see paragraph 4.1.6)

B. Location and orientation per design C. Clearances and tolerances per design D. Separation criteria E. End brushing F. Identification (labeling) ,

G. i H.

Cutting, bending, threading, deburring(conduit only;". :

Hot pipe separation I. No visible damage J.

Maximum bends between pull points (conduit only) '

4.3.S Limit Switch Settinn M.O.V. ONLY REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Vitness Points for ITS systems Attributes: ,

A. Limit switch set such that it actuates as required by procedure manual, instruction, 13JZZI004

\

s 4.3.9 Auxiliary Relav Cabinets REQUIRED QC HOLD POINTS for Safety-Related cabinets (DER-85-22)

Attributes:

A. Contacts free of debris B. Lugs not touching position indicators C. Protective covers installed D. Cabinet clean PyttWA q6 64;

~$

Q DOC. NO: QA02.02 REVISION: 2 PACE 34 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 25 of 40 4.3.10 Electrical tests /adiustments Required QC Vitness Points for Safety-Related systems Attributes:

A. Dimensional inspection (see paragraph 4.1.5)

B. Megar testing C. Hypot testing 4,4 Instrumentation Inspection Points

  • .4.2 h trument/Eculpment/Part Installation / Reinstallation S;y"y REQUIRED QC HOLD POINTS for Safety-Related systems Required Q0 Vitness Points for ITS systems Attributes:

A. Correct material (see paragraph 4.1.6)

B, Cleanness for tubing systems (see paragraph 4.1.2)

C. Location and crientation per design D. Leveling and alignment per desi5n E. Clearances ar.d tolerances per design F. Tightness of connections (see paragraph 4.1.4)

G. Lubricants (type, on AML)

H. Condition of mating surfaces I. For velded equipment (see section 4.5)

J. Rigr.ing (see paragraph 4.1.7)

O 'T

, 'l

? '

PV21WA 1644) __

~

DOC. NO: QA02.02 REVISION: 2 PAGE 35 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 26 of 40 4.4.2 Tubinr, Installation REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Witness Points for ITS systems Atttibutes:

A. Correct materia' (see paragraph 4.1.6)

B. Internal cleanness (see paragraph 4.1.2)

NOTE: For 3/8" dia, and less, open end portions must be maintained with Fl'E closures (see paragraph 4.1.3)

C. Location and orientation xe.

1. flow direction (valves, orifices) ,,

D. Leveling and alignment

1. tube slope maintained E. Clearances and tolerances F. Correct bending tool used (bend radius)

G. Tightness of connections (see paragraph 4.1.4)

(Swagelok fittings verification is not required)

H.

As Built verification for new installations and ch:2nges to design 4.4.3 Flex Hose Installation Required QC Witness Points for Safety-Related systems Attributes:

A. Location and orientation per design B. Correct material (see paragraph 4.1.6)

C. Cleanness (sea paragraph 4.1.2)

D. Correct level and alignment (check anti torque lines)

E. Tightness of connections (see paragraph 4,1.4)

PY211HM A (&M }

gra.,

'i .. " ; DOC. NO: QA02.02

REVISION: 2 PACE 36 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 27 of 40 4.4.4 Tube / Component Supports REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Witness Points for ITS systems Attribu,tes :

A. Configuration / location /erientation per design B,

Clearance and tolerance per design C. Level and alignment per design D. Correct material (see paragraph 4.1.6)

E. Locking devices installation F. Weld inspection (see section 4.5) f'y_" , G. Anchor bolts (see paragraph 4.6.1)

H. Clamps U-bolts

1. Clamp snug on pipe
2. Bolts / nuts tightened (see paragraph 4.1.4)
3. Lock device if required installed 4.4.5 Terminatiens REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Vitness Points for ITS systems Attributes:

A. Correct material (see paragraph 4.1.6)

B. Termination tool C. Termination landing points D. Separation criteria -

E. Training / bend radius F. Identification (carking on wire / cable)

G. Tightness of connection (see paragraph 4.1.4)

H. Cable / conductor prep (strippin5 and cutting)

I. Wire penetration (e.g., into lug / connector / splice)

J. Heat shrink installation (see paragraph 4.4.8)

K Soldering (see paragraph 4.4.7)

L. Final visual M.

Flex conduit (reinstallation / installation)

{f N. Termination support PV71bOSA 44 44)

. 1

'E2g

,/ e DOC. NO: QA02.02 ;!

REVISION: 2 ~l PACE 38 0F SO '

DATE: 06/21/E8 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 29 of 40 4.4.8 Heat Shrink Attributes:

A. Correct material (see paragraph 4.1.6)

B. , Termination (see parngraph termination 4.4.5)

C. Cable / wire preparation D. Shims installed E. Final visual 4.4.9 Pressure Testing (excluding ILRT, LLRT or thore pressure test applicable to ASME Section XI.)

  • 7q

~ ~g REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Witness Points for ITS Attributes:

A. System walkdown to design documents B. H&TE verification, range requirements C. Appropriate pressures, temperatures D. Water chemistry (when applicable)

E. Bubble solution (when applicable)

F. Time at test pressure G. Visual / Bubble inspection / test results H. Instrumentation and items external to test bounda ry are isolated during testing I. Overpressuritation protection i

' J. Caging and ungaging of relief valves K. Supports have hydrostatic pins installed and recoved i

where applicable (see paragraph 4.2.3) l L. Post-test cleanliness l

l

.. ,/

DMA (&44) l l

~ ,I DOC. NO: QA02.02 REVISION: 2 .

PAGE 37 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 28 of 40 4,4,6 Cable / Wire Ins talla tion / Reins talla tion REQUIRED QC HOLD POINTS for Safety Related systems Required QC Ultness Points for ITS systems Attributes:

A. Correct material (see paragraph 4.1.6)

B. Routing C. Separation criteria D. Raceway preparation E. Pulling preparation F. Lubrication C. Cable pull tags <e.

H. Reel number I. Cable end cap scaled ( ~

J. Bend radius K. Cable ties 4.4.7 Soldering REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Witness Peints for ITS systems Attributes: (prior to soldering)

A. Correct solder material (type)

B. Correct cleaning material (type)

C. Correct soldering equipment (rating, heat sinks)

D. Cleanness (area, material) -

Attributes: (during soldering)

E. Per site / vendor requirements F. Heatsinks in place Attributes: (after soldering)

G. Final visual .

~

DOC. NO: QA02.02 REVISION: 2 PAGE 39 or 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A PaSe 30 of 40 4.5 Special Process Inspection Points 4.5.1 Heat treatment (Flame or Electrical resistance)

REQUIRED QC HOLD POINTS for Safety-Related items Required QC Witness Points for ITS items Attributes:

A. Thermocouple location B. Review of charts or manual recordings

1. Temperature rate of rise
2. Holding temperature range and time
3. Rate of cooling ,a C. Removal of thermocouples

4.5.2 Pine 'w'elding - Open butt, socket veld, seal weld, branch connections, fillet welds, or other welding covered under piping codes or specifications.

REQUIRF.D QC HOLD POINTS for Safety-Related items Required QC Vitness Points for ITS items Attributes: (prior to welding root pass)

A. Correct material (Spec. and grade)

B. Cleanliness (weld area)

C. Joint design

1. Veld preps (Bevel angle, root gap, root face)
2. Socket depth (Minimum per ANSI B16.ll, on cutouts weld build up)
3. Equal thickness transition (3 to 1 taper) 4 Socket pullout (1/16' nininum, scribe marks can be used)

PV71 M A % ', -=.

,(~',3

'.L. " D0C. NO: QA02.02 REVISION: 2 PAGE 40 0F $0 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 31 of 40 D< Preheat E. Purge dam installation F. Purge (oxygen %)

C. Ucid rod (type and size)

H. Velder qualification I. , Location and orientation J. Valve position (open or closed)

K. Fit up (mismatch and tacks)

(inprocess)

L. Interpass te=perature (for materials with impact test requirements)

,~s M.

". Backgouge (final)

N. Alignment (distortion)

O. Final visual (per applicable code)

P. Contour (unequal leg, transition)

Q. Post veld heat treatment R. Purge dam removal S.

Joint identification on material (weld ID) 4.5.3 Structural Veldinr /HVAC (Full penetration, partial penetration, fillet, plug, slot.)

REQUIRED QC h0LD POINTS for Safety-Related items Required QC Vi: ness Points for ITS items a

Attributes: (prior to welding root pass)

A. Correct material (Spec. and grade)

B. Cleanliness (weld area)

C. Joint design

1. Veld preps
2. Equal thickness transition
3. Clearances and alignment (Cap on fillet veld after welding if backside of member is exposec)

Py?1W A 14 44;

~

DOC. NO: QA02,02 REVISION: 2 .

PAGE 41 OF 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 32 of 40 D. Weld rod (type and size)

E Welder qualification F. Preheat C. Fit up (mismatch and tacks)

- (inprocess)

H. Backgouge I.

Interpass temperature (quenched or tempered caterials only)

(final)

J. Final visual (NCIC-01)

K. je.

Post weld heat temperature y; 4.5.4 Hardsurfacinn REQUIRED QC HOLD POINTS for Saf ety-Related items Required QC Vitness Points for ITS items Attributes: (prior to welding)

A. Cleanliness (Base metal preparation)

B. Weld rod (Type and size)

C. Welder qualification D. Preheat (final)

E. Final visual (per applicable code and after preparation for service) 9 kl }

,7;g DOC. NO: QA02.02

'q;. "

REVISION: 2 PACE 42 0F 50 DATE: 06/21/85 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 33 of 40 4.5.5 Tube plun veldinn REQUIRED QC HOLD POINTS for Safety Related items Required QC Witness Points for ITS items Attribu,tes: (prior to welding)

A. Material verification (final)

B. Plug location C. Ucider qualification a

I)

v. -

4.5.6 Brazing REQUIRED QC HOLD POINTS for Safety-Related items Required QC Witness Points for ITS items Attributes: (prior to brating)

A. Correct material B. Cleanliness (Bra:ing area)

C. Joint desi5n (length of lap, gap)

D. Filler material (type and si:c)

E. Brater qualification (final)

F. Final (to applicable code) -

C. Post cleaning (flux removal) l L.

Py?1603A gg44)

1

~

DOC. NO: QA02.02 REVISION: 2 .

PAGE 43 0F 50 DATE: 06/21/88 Arl.tona Nuclear Power Project TITLE: SUALUT CONTROL INSPECTIONS Appendix A Page 34 of 40 4.5.7 Ense Metal Repair Attributes: (prior to welding)

REQUIRED QC HOLD POINTS for ASME Class I only A,

Measurement of prepared cavity (depth, vidth, length)

B. Location of cavity REQUIRED QC HOLD POINTS for Safety-Related items Required QC Vitness Points for ITS items C. Preparation of cavity (smooth surfaces, cavity angle, contoured bottom) <-

D. Veld rod (type and size)

E. Welder qualification ~

F. Preheat G. Electrode storage if applicable (Ref. ASME Section XI I'w'B-4000)

H. Valve position (open/ closed)

(inprocess)

1. Inspection of cavity (if buttered using half bead technique)

J. Interpass temperature (materials with impact test requirements)

(Final)

K. Final weld L. Post veld heat treatment i

I l

evtts+na iem; l

C3 DOC. .i0: QA02.02 Qs REVISION: 2 PAGE 44 OF 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 35 of 40 4.5.8 Ueld Metal Repair REQUIRED QC 110LD POINTS for Safety-Related items Required QC Vitness Points for ITS items Attribu,tes : (prior to welding rootpass)

A.

Preparation of cavity (smooth surfaces, cavity angle, contoured bottom)

B. Purge (oxygen %)

C. Veld rod (type and size)

D. Welder qualification E. Preheat

, F. ,dve position (open/ closed)

E)

(inprocess)

C. Interpass temperature (materials with impact test requirements)

Required QC Vitness Points for ITS systems 11 .

Final weld (per applicabic code)

1. Contour (unequal leg, transition)

J. Post veld heat treatment K Purge dam removal L.

Joint identification on material (Weld ID)

[ - -

I

  • evne.ona is m, i

DOC. NO: QA02.02 REVISION: 2 PAGE 45 0F 50 (, l DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 36 of 40 4.6 Civil Inspection Points 4.6.1 Anchor bolts REQUIRED QC HOLD POINTS for Safety-Related systems Required QC Vitness Points for ITS systems Attributes:

A. Angle of installation (hole or anchor)

B. Correct material (see paragraph 4.1.6)

C. Location and orientation D. Hole undercut (Drilco maxi only)

E. Torque (setting / installation) ,,

4.6.2 Coatings REQUIRED QC HOLD POINTS for all coatings inside contain=ent and ID of safety-related piping cocponents.

Attributes:

A. Correct material (see paragraph 4.1.6)

B. Batching / mixing C. Surface preparation

1. anchor profile
2. cleanliness D. Atmospheric conditions (prior to coating)

E. Painter qualification F. Coating thickness (wet or dry film) -

C. Final visual 4.6.3 Concrete and Masonrv Coredrillinn REQUIRED QC HOLD POINTS for all permanent plant structures.

Attributes:

A. Cut rebar documentation was-cu +ui

--- ~

+<

M' ' - DOC. NO: QA02.02 REVISION: 2 PACE 46 0F 50 DA E: 06/21/88 Arizona Nuclear Power Pro, lect TITLE: QUALITY CONTROL INSPECTIONS Appendix A Page 37 of 40 4.6.4 Cadweld Splicing REQUIRED QC HOLD FOINTS for all safety related structures.

Attributes:

A. -

Qualification of Cadwelders B. Correct caterial (see paragraph 4.1.6)

C. Location and orientation D. Setup (clean, centering, markings)

E. Final visual F. Tensile testing 4.6.5 Reinforcint Steel REQUIRED QC HOLD POINTS for all permanent plant structures.

Attributes:

A. Correct Material (size and grade)

B. Splicing (lap non-contact)

C. Clear Distance D. Location and Orientation 4.6.6 Structural f, teel (Fab and Installation)

REQUIRED QC HOLD POINTS for all safety related structures.

Required QC Witness Points for ITS structures.

Attributes: '

A. Location and orientation B. Correct material (see paragraph u.1.6)

C. Configuration of fabrication / installation D.

Tightness of connection (see paragraph 4.1.4)

E. Rigging (see paragraph 4.1.7)

F. Welding (see section 4.5)

')

PV216 C8A (444)

DOC. NO: QA02.02 J

REVISION: 2 PAGE 47 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CONTROL INSPECTIONS l

Appendix A Page 38 of 40 4.6.7 Croutinn REQUIRED QC HOLD POINTS for all safety-related structures.

Required QC Witness Points for ITS structures.

QC Hold-Point to perform Grout testing for quality related installations.

Attributes:

A. Surface preparation B. Presoak C. Forms D. Mixing E. f".9 Correct material (see paragraph 4.1.6)

F. Placement requirements ',c;l G. Curing H. Final visual (cracking, damage) 4.6.8 Concrete REQUIRED QC HOLD POINTS for all safety-related installations.

Required QC Witness Points for ITS installations.

QC Hold Point to perform Concrete testing for quality related installations.

Attributes:

A. Cleanliness of equipment -

B. Material testing (slu=p, unit vt)

C. Correct materials (mix design)

Attributes: (preplacement activities)

D. Surface / construction joint pre E. Formwork/ subgrades F. Rebar/ embed installed C. C1canliness (rebar, forms) -

%d l f

i e

  • Ih DOC. NO: QA02.02 REVISION: 2 PAGE 48 OF 50 l DATE: 06/21/88 i -

Arizona Nuclear Power Project l

TITLE: QUALITY CONTROL INSPECTIONS l

Appendix A l Page 39 of 40 l Attributes: (placement activities)

H. Cleanliness of placing equipment

1. Testing / sampling J. Consolidation methods and convey methods i

! Attributes: (post-placement activities)

K. Curing methods L. Finish (rock pockets, honeycomb) l l 4.'.9 Fire Proofinn (i.e., Penetration Seals, Thermo-lag, Fire Doors and Monokota)

[Ij REQUIRED QC HOLD POIh'TS for activities identified as required

[G9J1 in the applicable specifications.

j 4.6.9,1 Penetration Sealant i

Attributes:

A. Correct materials (see paragraph 4.1.6)

B. Cleanliness C. Testing D. Configuration E. Final visual 4.6.9.2 Thermo-lat Attributes: ,

A. Correct material (see paragraph 4.1.6)

E. Surface Prep C. Primer / adhesion testing D. Curing E. Material thickness F. Final visual

,e..

'k- l Py?1W A (W3

DOC. NO: QA02.02 .-

REVISIO;?: 2 PAGE 49 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALITY CO!TTROL INSPECTIONS Appendix A Page 40 of 40 4.6.9.3 Fire Door Attributes:

A. Correct materials (see paragraph 4.1.6)

. B. Clearances C. Hardware installation / function l D. Damage (i.e., holes, door skin loose) l 4.6.9.4 Sprav on fire proofig (Monokote)

Attributes:

A. Correct materials (see paragraph 4.1.6) -

B. Material thickness 4.6.10 Soils REQUIRED QC HOLD POINTS for all backfill within the protected area.

Attributes:

A. Area properly prepared for backfill B. Material Testing (compaction, gradation)

C. Correct fill D. Materials properly placed and co=pacted

$ A INj

  • q

.:.C9 DOC. NO: QA02.02

  1. REVISION: 2 PAGE 50 0F 50 DATE: 06/21/88 Arizona Nuclear Power Project TITLE: QUALIIT CONTROL INSPECTIONS 1

l Appendix B i

Page 1 of 1

!l INSPECTION HOLD POINT / WITNESS POINT RELEASE FOR.M l Word DOCUMENT PROCEDLU. NO: 1%E OF l; I

1 J5U Pl A URIBLTES / INSPECTION PLAN i l No l l j....l..................................

1 1 1l......................................ll I

l } i l hA".E : DAR :

1 t l i

I i 1 i

l l I l Acceptable Unacceptable l l l l i I i

l i I

-' lNAMI: D ATT. :

l l l l

1 1 1 I

{ I

{ l Acceptable Unacceptablel

-1 I l 1

1 I

i I I i l l  ! l

}NA"1: DATE: l l I I

I I I I

{ j I l Acceptable Unacceptabiel i l I i i I i

! I l  ! I I

l t 1 l NA."l: DATE: l 1 i i i I l

l 1 l [ Accepthble l

] Unacceptablel l l '

I I I I

I 1 l I i

I j  ! L lNA"I: DA*E: l I I I I I I I I

l l Acceptable I

l Lnacceptablel I  !

i 1 I I

I PV71W A (s m)

((f Arizoria Nuclear Power Project AWX, f COMPANY CORRESPONDENCE g,,, on nsV lll2 l$ 1 * .a s IDI 203-00134/FCB l} Q/ I

I

//I,/TSp orts 7/5/88 y1 4 <.

e O / y/e to W.E. Ide h c.; @ u n su a 6452 ta = 2366 g & ,{, pQ FRoM FrankC.Buckingham[ y s:. . 6451 Ena 2220 .

FILE:

suestcT 88-159-419 Use of Lighting Prints' for C4eart.nces '

, 7[/

/ ll The station lighting prints ar\e (3 series prints as opposed to the as--

built prints which we have for other systems. This requires the issuino organization on a' clearance to perform exhaustive research in order to ensure the adequacy of a ciegranc'e. Dhich in turn increases the likelihood of an inadequate clearance resulting in a hich cotential for an electrical thoek hazard. This practice oftnot having as-built lighting prints has been condoned for years and was.somewhat justifiabic during the startup phase. Now that all 3 units are completed I believe that the 13 series s

lighting prints have outlined the Q useful, ness and present a safety _

hazard. The safetv of clant a m nnnal and proper configuration control

' demand that station lighting prints be issued as unit specific as-built prints.

FCB/tw ,

cc: J. Haynes G. Sowers 9@@hbgg R. tlutler -

E. Sterling i D. Gouge g g g33 ww-R. Younger tucmEERING DifN y/

I]$

s, l '

____pg. yL _j. ,y

__